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Analysis of Rotor-Seizure-Induced Pressure Rise in a Nuclear Reactor Primary Cooling Loop

by Haoyu Cui1, Congxin Yang1,2,*, Yanlei Guo1, Tianzhi Lv1, Sen Zhao1

1 College of Energy and Power Engineering, Lanzhou University of Technology, Lanzhou, 730050, China
2 Key Laboratory of Fluid Machinery and System of Gansu Province, Lanzhou, 730050, China

* Corresponding Author: Congxin Yang. Email: email

(This article belongs to the Special Issue: Computational Fluid Dynamics: Two- and Three-dimensional fluid flow analysis over a body using commercial software)

Fluid Dynamics & Materials Processing 2024, 20(12), 2907-2926. https://doi.org/10.32604/fdmp.2024.055301

Abstract

Most of existing methods for the safety assessment of the primary cooling loop of nuclear reactors in conditions of reactor coolant pump (RCP) failure (rotor seizure accident) essentially rely on the combination of one-dimensional theory and experience. This study introduces a novel three-dimensional model of the ‘Hualong-1’ (HPR1000) primary loop and uses the method of matching the resistance characteristics of the tube to ensure that the main pump operates at the rated operating condition. In particular, the three-dimensional unsteady numerical calculation of the RCP behavior in the rotor-seizure accident condition is carried out in the framework of the RNG k-ε turbulence model. The related transient pressure surge law and hydraulic load response are obtained accordingly.

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APA Style
Cui, H., Yang, C., Guo, Y., Lv, T., Zhao, S. (2024). Analysis of rotor-seizure-induced pressure rise in a nuclear reactor primary cooling loop. Fluid Dynamics & Materials Processing, 20(12), 2907-2926. https://doi.org/10.32604/fdmp.2024.055301
Vancouver Style
Cui H, Yang C, Guo Y, Lv T, Zhao S. Analysis of rotor-seizure-induced pressure rise in a nuclear reactor primary cooling loop. Fluid Dyn Mater Proc. 2024;20(12):2907-2926 https://doi.org/10.32604/fdmp.2024.055301
IEEE Style
H. Cui, C. Yang, Y. Guo, T. Lv, and S. Zhao, “Analysis of Rotor-Seizure-Induced Pressure Rise in a Nuclear Reactor Primary Cooling Loop,” Fluid Dyn. Mater. Proc., vol. 20, no. 12, pp. 2907-2926, 2024. https://doi.org/10.32604/fdmp.2024.055301



cc Copyright © 2024 The Author(s). Published by Tech Science Press.
This work is licensed under a Creative Commons Attribution 4.0 International License , which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited.
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